Gas-cooled Reactor Program
Author : F. J. Homan
Publisher :
Page : 310 pages
File Size : 50,28 MB
Release : 1981
Category :
ISBN :
High-temperature Gas-cooled Reactor Technology Development Program. Annual Progress Report for Period Ending December 31, 1980
Author :
Publisher :
Page : 310 pages
File Size : 10,87 MB
Release : 1981
Category : Gas cooled reactors
ISBN :
Book Description
Research activities are described concerning HTGR chemistry; fueled graphite development; prestressed concrete pressure vessel development; structural materials; HTGR graphite studies; HTR core evaluation; reactor physics; shielding; application and project assessments; and HTR Core Flow Test Loop studies.
High-Temperature Gas-Cooled Reactor Technology Development Program
Author :
Publisher :
Page : 164 pages
File Size : 20,1 MB
Release : 1989
Category :
ISBN :
Book Description
The High-Temperature Gas-Cooled Reactor (HTGR) Program being carried out under the US Department of Energy (DOE) continues to emphasize the development of modular high-temperature gas-cooled reactors (MHTGRs) possessing a high degree of inherent safety. The emphasis at this time is to develop the preliminary design of the reference MHTGR and to develop the associated technology base and licensing infrastructure in support of future reactor deployment. A longer-term objective is to realize the full high-temperature potential of HTGRs in gas turbine and high-temperature, process-heat applications. This document summarizes the activities of the HTGR Technology Development Program for the period ending December 31, 1987.
Energy Research Abstracts
Author :
Publisher :
Page : 852 pages
File Size : 37,55 MB
Release : 1990
Category : Power resources
ISBN :
Book Description
High-temperature Gas-cooled Reactor Technology Development Program. Annual Progress Report for Period Ending December 31, 1982
Author :
Publisher :
Page : pages
File Size : 11,31 MB
Release : 1983
Category :
ISBN :
Book Description
During 1982 the High-Temperature Gas-Cooled Reactor (HTGR) Technology Program at Oak Ridge National Laboratory (ORNL) continued to develop experimental data required for the design and licensing of cogeneration HTGRs. The program involves fuels and materials development (including metals, graphite, ceramic, and concrete materials), HTGR chemistry studies, structural component development and testing, reactor physics and shielding studies, performance testing of the reactor core support structure, and HTGR application and evaluation studies.
Gas-cooled Reactor Programs
Author :
Publisher :
Page : pages
File Size : 49,25 MB
Release : 1982
Category :
ISBN :
Book Description
Information is presented concerning HTGR chemistry; fueled graphite development; irradiation services for General Atomic Company; prestressed concrete pressure vessel development; HTGR structural materials; graphite development; high-temperature reactor physics studies; shielding studies; component flow test loop studies; core support performance test; and application and project assessments.
PUBLIC SERVICE COMPANY OF COLORADO 330-MW(e) HIGH-TEMPERATURE GAS-COOLED REACTOR RESEARCH AND DEVELOPMENT PROGRAM. Quarterly Progress Report for the Period Ending December 31, 1969
Author :
Publisher :
Page : pages
File Size : 46,14 MB
Release : 1970
Category :
ISBN :
Book Description
Public Service Company of Colorado 330-MW(E) High-Temperature Gas-Cooled Reactor Research and Development Program. Quarterly Progress Report for the Period Ending December 31, 1970
Author :
Publisher :
Page : pages
File Size : 30,16 MB
Release : 1971
Category :
ISBN :
Book Description
High-temperature Gas-cooled Reactor Base-technology Program Annual Progress Report for Period Ending December 31, 1979
Author :
Publisher :
Page : 276 pages
File Size : 13,28 MB
Release : 1980
Category :
ISBN :
Book Description
Advanced Gas Cooled Nuclear Reactor Materials Evaluation and Development Program. Progress Report for Period October 1, 1980-December 31, 1980
Author :
Publisher :
Page : pages
File Size : 14,97 MB
Release : 1981
Category :
ISBN :
